Collaborative flowsheet development studies using cobalt dicarbollide and phosphine oxide for the partitioning of radionuclides from Idaho Chemical Processing Plant high-activity liquid waste with centrifugal contactors

Two solvent extraction technologies under development in Russia for the partitioning of radionuclides from radioactive wastes were tested at the Idaho Chemical Processing Plant (ICPP) with simulated high-activity liquid waste (HAW) on a continuous basis using 24 stages of 2-cm diameter centrifugal contactors. Two flowsheet tests were conducted with chlorinated cobalt dicarbollide (ChCoDiC) to evaluate the separation of cesium and strontium from ICPP HAW. Also, a flowsheet test was performed with a derivative of phosphine oxide (POR) to evaluate the separation of actinides, rare earths, and technetium from ICPP HAW. All experiments utilized a non-radioactive HAW simulant prepared to emulate the macro (or matrix) constituents of actual ICPP HAW at their average tank composition. The behavior of the species of interest was monitored using the stable forms of Sr and Cs, europium as a surrogate for americium, and rhenium as a surrogate for technetium. Removal efficiencies and distribution coefficients were determined for each flowsheet at steady-state conditions. Results of this testing indicate the POR and ChCoDiC processes can be used to effectively treat ICPP HAW. This series of tests is a continuation of ongoing efforts to evaluate the applicability of these Russian developed technologies to U.S. nuclear wastes under the auspices of a joint program between the U.S. Department of Energy and the Russian Ministry of Atomic Energy